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This page provides a simple browsing interface for finding entities described by a property and a named value. Other available search interfaces include the page property search, and the ask query builder.
List of results
- PNO-V-89-046, on 890806,reactor Tripped from 100% on Low Reactor Pressure Vessel Water Level.Cause of Loss of Lube Oil Pressure & Reactor Trip Under Investigation.Plant Expected to Be Shutdown Until 890809 for Repairs + (10:54:56, 8 January 2025)
- 05000397/LER-1989-029, :on 890703,RWCU & RCIC Sys Isolation Occurred When RWCU-V-1 Closed as Part of Group 7 Nuclear Steam Supply Shutoff Sys Isolation.Caused by Inadequate Preparation & Review of Surveillance Test Procedure + (10:54:57, 8 January 2025)
- IR 05000397/1989006 + (10:54:59, 8 January 2025)
- ML17285A655 + (10:55:00, 8 January 2025)
- ML17285A653 + (10:55:01, 8 January 2025)
- IR 05000397/1989022 + (10:55:02, 8 January 2025)
- GO2-89-133, Submits Final Response to Suppl 1 to NRC Bulletin 85-003. Measured Thrust Values for Valves Obtained by Analysis of Spring Pack Calibr Signatures & Valves Controlled by Limit Switches W/Open Torque Switches Jumpered Throughout Travel + (10:55:04, 8 January 2025)
- ML17285A650 + (10:55:04, 8 January 2025)
- IR 05000397/1989016 + (10:55:07, 8 January 2025)
- ML17285A646 + (10:55:08, 8 January 2025)
- 05000397/LER-1989-028, :on 890629,turbine Throttle Valve Closure Reactor Scrammed During Turbine Testing.Caused by Inadequate Procedure.Operator Acted Promptly Tp Place Plant in Safe Shutdown Condition.Training Program Improved + (10:55:11, 8 January 2025)
- GO2-89-128, Forwards Instrument Air Sys Review Response to Generic Ltr 88-14, Per 890706 Commitment + (10:55:13, 8 January 2025)
- ML17285A641 + (10:55:13, 8 January 2025)
- GO2-89-129, Responds to NRC Re Violations Noted in Insp Rept 50-397/89-13.Corrective Actions:Radiation Barrier Posting for RWCU HX Room Removed from accordion-style Gate at Entrance to Room & Placed on Rope in Front of Gate + (10:55:15, 8 January 2025)
- GO2-89-127, Responds to Generic Ltr 89-06, SPDS, Certifing That Graphic Display Sys Fully Meets Requirements of NUREG-0737, Suppl 1,taking Into Account Info Provided in NUREG-1342 + (10:55:17, 8 January 2025)
- ML17285A636 + (10:55:17, 8 January 2025)
- GO2-89-120, Provides Addl Info Re Acceptability of Five Installed Items for Use in safety-related Applications,Per Insp Rept 50-397/89-21.Items Include,Potter & Brumfield Relays,Anchor Darling Valve Parts & 600 Volt or Less Fuses + (10:55:19, 8 January 2025)
- GO2-89-125, Advises That No Agreements Exist That Contain Restrictive Clauses Re Employee Right to Discuss Potential Safety Issue + (10:55:20, 8 January 2025)
- 05000397/LER-1989-026, :on 890619,testing Confirmed That Selected Steam Tunnel Penetrations Could Fail to Perform as Pressure Boundary Following Design Basis Main Steamline Break.Caused by Inadequate Design Mgt.Part 21 Related + (10:55:22, 8 January 2025)
- 05000483/LER-1917-002, Regarding Inadequate Protection from Tornado Missiles Identified Due to Nonconforming Design + (10:55:25, 8 January 2025)
- GO2-89-123, Forwards Addl Info Re 880726 Response to Generic Ltr 88-01, Per NRC 890516 Request + (10:55:25, 8 January 2025)
- ML17285A628 + (10:55:27, 8 January 2025)
- ML17285A627 + (10:55:28, 8 January 2025)
- 05000397/LER-1989-025, :on 890617 & 18,three Separate But Related Events Occurred Which Caused ESF Isolations & Actuations During Excess Flow Check Valve Testing.Caused by Inadequate Procedure.Procedure Modified + (10:55:29, 8 January 2025)
- IR 05000397/1989018 + (10:55:31, 8 January 2025)
- ML17285A623 + (10:55:32, 8 January 2025)
- 05000397/LER-1989-024, :on 890614,secondary Containment Bypass Leakage Found Greater than Allowed by Design Basis.Caused by Equipment Design Deficiency.Check Valves in Common Discharge Line of CRD Pump Installed to Prevent Leakage + (10:55:33, 8 January 2025)
- GO2-89-119, Responds to Concerns Noted in Insp Rept 50-397/89-01 Re Implementation of Root Cause Analysis (RCA) Program & RCA Rept Prepared for 890311 Rod Drift Event.Plans to Combine Elements of Process & Document Results in Incident Rept + (10:55:34, 8 January 2025)
- ML17285A620 + (10:55:34, 8 January 2025)
- GO2-89-118, Provides Justification for Continued Use of Five Installed Items Identified in Insp Rept 50-397/89-21,in Response to Bh Faulkenberry .Final Results & Assessment of Addl Commercial Grade Items Will Be Provided by 890815 + (10:55:36, 8 January 2025)
- IR 05000397/1989013 + (10:55:43, 8 January 2025)
- ML17285A613 + (10:55:45, 8 January 2025)
- ML17285A616 + (10:55:45, 8 January 2025)
- ML17285A612 + (10:55:47, 8 January 2025)
- ML17285A610 + (10:55:47, 8 January 2025)
- GO2-89-116, Advises That Final Response to Generic Ltr 88-14, Instrument Supply Sys Problems Affecting Safety-Related Equipment, Including Outage Test Results,Will Be Provided by 890728 + (10:55:48, 8 January 2025)
- ML17285A607 + (10:55:50, 8 January 2025)
- 05000397/LER-1989-020, :on 890527 & 0605,during Local Leak Rate Testing,Valve RHR-V-9 Automatically Isolated.Caused by Procedural Inadequacy & Inadequate Corrective Action Following Second Event.Procedure Modified + (10:55:51, 8 January 2025)
- 05000397/LER-1989-022, :on 890530,loss of Secondary Containment During Core Alterations Due to Unisolatable Lines Occurred.Caused by Simultaneous Activities.Rhr Heat Exchanger Isolation Valves Closed to Reestablish Integrity + (10:55:54, 8 January 2025)
- 05000397/LER-1989-023, :on 890531,ESF Isolations & Actuations Occurred Due to Loss of Reactor Protection Sys Bus During Testing. Caused by Personnel Error.Logic Sys Functional Test Procedure Revised.Test Engineer Counseled + (10:55:55, 8 January 2025)
- IR 05000397/1989021 + (10:56:00, 8 January 2025)
- ML17285A596 + (10:56:02, 8 January 2025)
- ML17285A597 + (10:56:02, 8 January 2025)
- GO2-89-114, Application for Amend to License NPF-21,modifying Tech Spec Tables 3.3.7.5-1 & 4.3.7.5-1 Re Accident Monitoring Instrumentation & Surveillance Requirements + (10:56:03, 8 January 2025)
- IR 05000397/1989014 + (10:56:06, 8 January 2025)
- ML17285A585 + (10:56:07, 8 January 2025)
- 05000397/LER-1989-021, :on 890527,electrical Protection Assembly Breaker Tripped Causing Loss of Power to Reactor Protection Sys Bus B.Cause Unknown.Upgraded Breaker Equipment Will Be Installed + (10:56:08, 8 January 2025)
- IR 05000397/1989011 + (10:56:12, 8 January 2025)
- ML17285A581 + (10:56:13, 8 January 2025)
- ML17285A580 + (10:56:14, 8 January 2025)
- ML17285A579 + (10:56:15, 8 January 2025)